量子粒子群融合算法在放射源探测标定中的应用

为有效进行辐射剂量探测,设计了有源在线监控模块。针对监控模块辐射测量值标定这一难题,提出了基于量子粒子群的融合算法实现对测量值与剂量值之间的高精度逼近。使用聚类和数据融合算法实现了拟合数据的自主最佳分段,避免了分段选择的主观性。仿真结果表明,融合算法能有效减少计数率较小时拟合函数的误差,提高各数据段测量值与剂量率之间的拟合精度,与整体拟合函数相比,进一步提高了拟合的精度。     

量子粒子群融合算法在放射源探测标定中的应用

为有效进行辐射剂量探测,设计了有源在线监控模块。针对监控模块辐射测量值标定这一难题,提出了基于量子粒子群的融合算法实现对测量值与剂量值之间的高精度逼近。使用聚类和数据融合算法实现了拟合数据的自主最佳分段,避免了分段选择的主观性。仿真结果表明,融合算法能有效减少计数率较小时拟合函数的误差,提高各数据段测量值与剂量率之间的拟合精度,与整体拟合函数相比,进一步提高了拟合的精度。     

基于切比雪夫有理逼近方法的蒙特卡罗燃耗计算研究与验证

燃耗计算在反应堆设计、分析研究中起着重要作用。相比于传统点燃耗算法,切比雪夫有理逼近方法(Chebyshev rational approximation method,CRAM)具有计算速度快、精度高的优点。基于超级蒙特卡罗核计算仿真软件系统Super MC(Super Monte Carlo Simulation Program for Nuclear and Radiation Process),采用切比雪夫有理逼近方法和桶排序能量查找方法,进行了蒙特卡罗燃耗计算的初步研究与验证。通过燃料棒燃耗例题以及IAEA-ADS(International Atomic Energy Agency-Accelerator Driven Systems)国际基准题,初步验证了该燃耗计算方法的正确性,且IAEA-ADS基准题测试表明,与统一能量网格方法相比,桶排序能量查找方法在保证了计算效率的同时减少了内存开销。     

核电计算中刚性常微分方程的数值解

在核电计算中,核岛中的反应堆动态学方程和常规岛中的湿蒸汽汽轮机甩负荷时各级压力变化方程都是典型的刚性常微分方程。本文介绍用通用性强的Gear方法求解这些刚性方程的有效性。在解点堆动态学方程时,Gear方法的计算效率与分段多项式逼近法相当;在对矩阵求逆的算法作了改进后,该方法的计算效率就高于分段多项式逼近法。     

MC法模拟相对论逃逸电子雪崩理论机制

基于GEANT4软件完成闪电高能辐射RREA机制的模拟计算。采用有理数逼近的拟合方法,得到的雪崩距离常数、雪崩时间常数、光子数与逃逸电子数比值的计算公式,均为只有电场强度一个变量的函数,便于各个参数的理论计算和对比分析;评估了GEANT4中不同物理模型对仿真计算结果的影响,结果表明:构造函数EM Opt4采用的物理模型精度最高,输运相等的雪崩距,产生的轫致辐射光子最多,但计算过程耗费的时间也最长。     

用于pin-by-pin输运计算的SP_3解析基函数展开节块方法研究

基于三阶简化球谐函数(SP_3)方法,分别采用3种不同的偏流表达形式,开发了SP_3解析基函数展开节块程序。利用基准例题对程序进行了数值检验,并对3种偏流表达形式的计算精度进行了对比分析。数值结果表明:SP_3解析基函数展开节块方法应用于pin-by-pin输运计算时,能获得较高的棒功率计算精度;3种偏流表达形式中,Marshak偏流表达形式计算精度最高,另外两种偏流表达形式计算精度稍差,但更利于程序算法简化及并行算法设计。     

用解析和数值方法研究动量淀积深度分布

基于解析和数值两种方法,作者研究了Glazov于1994年提出的计算由原子弹性碰撞引起动量淀积的空间分布.本文证明了Glazov推导出的积微分方程是不正确的,因为其中将两个原本独立的变量"纠缠"起来.分布函数在靶表面的"奇点"正是由这种"纠缠"引起的.动量淀积分布函数所满足的传统Boltzmann输运方程与Glazov方程并不等价.所以,由Glazov方程推导出的一切结果就都成问题了.另一方面,作者证明了由Glazov同样的高精度计算(通常n=300阶矩,28位小数)精度不足以再现Glazov文中的大部分图表.在这个工作中,作者用Padé逼近以及更高精度(n=980阶矩,500位小数)计算了动量淀积分布函数的富利叶变换f(k,η)和fL(k).我们的数值计算结果表明:对于这类输运问题的研究,Padé逼近是一种强大的理论工具.     

瞬态曲线分段线性化方法研究及其程序实现

核电厂的瞬态数据是相关设备应力分析和评定的必要输入。然而,电厂实际运行记录数据或设计瞬态计算数据通常由时间间隔很短的大量数据点构成,直接作为应力分析的输入将会导致大量不必要的计算。为了简化分析,一般需要将瞬态数据曲线进行分段线性化处理。本文基于最小二乘法,开发了一种瞬态曲线分段线性化的方法,并且通过编写PLTC(PiecewiseLinearization forTransientCurves)程序予以实现。分别采用标准正弦函数曲线和核电厂典型瞬态曲线对本文的方法进行了验证,结果表明,本文的方法和程序能够很好地实现瞬态曲线的分段线性化。本文的研究有助于提高核电厂瞬态曲线分段线性化的效率和精度。     

RBF网络高斯型传输函数的FPGA实现

本文在研究CORDIC算法的基础上,在FPGA上实现了RBF网络的Gauss型传输函数,分析了该实现方法在输入为[-7 0]时的误差,并得出实现该函数的CORDIC迭代所需资源仅和同样字长的乘法器相当.当把CORDIC算法实现的传输函数用于解决XOR问题的RBF网络时,该网络也表现出良好的性能.     

反应堆负荷跟踪中氙瞬态响应的最优控制

反应堆氙瞬态响应是负荷跟踪过程中的主要问题之一,它关系到反应堆运行的弪济性和安全性。本文根据sTM(system Tau Metl,0d)求解线性优化问题不需迭代、速度快、精度高等特点,以及微分动态规铷DDP(Differential Dynamic Pr0一gramming)求解非线性优化问题时,在最优轨线领域很快收敛的特点,提出了先用sTM预估标称控制,然后再用DDP逼近非线性最优解的sTMDDP算法。计算表明,sTMDDP不仅有效地解决了非线性优化计算的收敛问题,而且与其它常用方法比较,在计算精度相同情况下,迭代次数减少,计算时间显著缩短。实例计算所得结论,对工程实际有重要参考价值。     

Preparation of Zn/TiO2 powder and its photocatalytic performance for oxidation of P-nitrophenol

Zn-doped TiO2 catalysts were prepared using a sol-gel method and characterized by XPS,UV-Vis, BET, XRD in this study. Under the irradiation of simulant sunlight, the photocatalytic activity for the degradation of p-nitrophenol was studied too. After irradiation for 2.5 h, the degradation percentage of p-nitrophenol could rise to more than 80 %. The results showed that the spectrum absorption band edge of Zn/TiO2 powder does not broaden obviously comparing with pure TiO2 powder. Zinc exists as Zn （11）. When calcined at 973 K, there is a new phase as ZnTiO3 in Zn/TiO2 catalyst. The order of photocatalytic activity of Zn/TiO2 catalysts calcined at different temperatures for p-nitrophenol is 773 K 〉 673 K 〉 873 K 〉 573 K 〉 973 K and the photocatalytic activity of Zn/TiO2 catalyst calcined at 773 K is better than TiO2 catalysts heated at the same temperature, and outclasses that of commercial TiO2 catalyst. It also showed that the photocatalytic degradation of p-nitrophenol follows first-order kinetics under the irradiation of simulant sunlight.     

Current status of radiation therapy for prostate cancer

Radiotherapy for the treatment of prostate cancer has been extensively explored in the past. Along with the comprehensive understanding of the biology of prostate cancer and rapid advances in terms of technology, the out- come of treatment for the patients with prostate cancer has improved. The authors review radiotherapy as the primary treatment for the disease, with particular emphasis on the technological advances from both the radiobiological and radiophysics aspects. Nonconventional fractionated irradiation like hyper- or hypo-fractionation has been imple- mented in the clinic, the final results still need to be confirmed in the future. Technological advances like IMRT, IGRT, in the last two decades have significantly improved the delivery of external radiotherapy to the prostate. This has re- sulted in an overall increase in the total dose that can be safely delivered to the prostate, which has led to modest im- provements in the biochemical outcome. However, establishing the standard therapy for prostate cancer remains con- troversial. It is hoped that the next decades will bring continued advances in the development of biologicals that will further improve current clinical outcomes.     

The control system for SSRF injection and extraction

This paper introduces the injection and extraction control system design for SSRF,which is a distributed control system aimed at stability and reliability of the pulse power supplies,PPS(Personnel Protection System)and MPS(Machine Protection System).The hardware environment is mainly based on PLC(Programmable Logic Con- troller),and ARM(Advanced RISC Machine)is also applied for studying stability of the power supplies.WinCC and EPICS(Experimental Physics and Industrial Control System)have been selected as the platforms of SCADA(Super- visory Control and Data Acquisition).For unifying the interfacing to the control computer,all front-end equipments are connected via Industrial Ethemet.     

水平管内含空气蒸汽强制对流冷凝换热模型研究

为研究含空气蒸汽在水平管内强制对流冷凝换热特性,基于对传热传质过程的分析,建立了管内为环状流与波状流条件下的流动冷凝换热模型。从潜热、显热和液膜3个环节对整个换热过程进行建模,最终得到计算局部冷凝换热系数的理论关系式。模型预测结果与实验数据的对比表明,二者相对偏差在±20%以内,验证了该换热模型的准确性与适用性。通过进一步的研究发现：从换热管入口至出口,随着冷凝的进行,管内换热主要热阻由液膜热阻向气液界面的凝结热阻转变;主流气体对流换热过程基本可忽略。     

有效探测面积大于1000 cm2的正比计数器测量系统性能测试

为对自制的活性面积高达1 000 cm²的大面积源进行表面发射率定值,同时作为现有2πα、2πβ表面发射率标准装置能力的扩充,研制了一套内置式大面积2π多丝正比计数器测量系统,并利用活性区直径为8 mm的²⁴¹Am点源及活性区面积为10 cm×15 cm的大面积²⁴¹Am和⁹⁰Sr-⁹⁰Y源对其进行计量学性能测试。结果表明：计数器内计数响应均匀性优于±0.4%,有效探测面积达1 400 cm²;所得²⁴¹Am源高压坪曲线的坪长为1 400 V,坪斜为0.27%/100 V,坪区内计数变化为0.87%;⁹⁰Sr-⁹⁰Y源高压坪曲线的坪长为300 V,坪斜为0.75%/100 V,坪区内计数变化为0.80%;10次测量重复性好于0.4%,8 h内短期稳定性好于0.3%,1 a内长期稳定性好于0.8%。     

Investigations on landmine detection by BF3 detector

Experiments were carried out to investigate the possible use of neutron backscattering for the detection of polyethylene (PE) sample buried in the soil. In detection of landmine by neutrons, the neutron detector and its shield play an important role. In this paper, the effects of graphite, heavy water, polyethylene and boric acid moderators on the flux of back scattered neutrons were investigated. We have also experimentally verified the effect of BF3 detector shield and obtained good agreement with theory.     

Web Services interface of SSRF archive data analysis system

Accelerator database stores various static parameters and real-time data of accelerator. SSRF (Shanghai Synchrotron Radiation Facility) adopts relational database to save the data. We developed a data retrieval system based on XML Web Services for accessing the archive data. It includes a bottom layer interface and an interface applicable for accelerator physics. Client samples exemplifying how to consume the interface are given. The users can browse, retrieve and plot data by the client samples. Also, we give a method to test its stability. The test result and performance are described.     

Assessment of radioactivity levels in some oil samples from the western desert, Egypt

Distributions of natural gamma-emitting radionuclides were determined in 93 oil samples collected from some petroleum fields in the western desert of Egypt. The radioisotope activities in the area under investigation lay in the range of (21 ± 4) to (38 ± 13) Bq?L-1 for 226Ra, (9 ± 2) to (15 ± 5) Bq?L-1 for 232Th, and (154 ± 28) to (303 ± 54) Bq?L-1 for 40K. The mean values were 27, 12, and 201 Bq?L-1, respectively. Among oils, variations in radionuclide ac- tivities could be on account of differences in TDS, HCO3, and Ba, with high or low pH. In this environment, oil prop- erties differently affected the mobilization of natural radionuclides. The range of 226Ra variation had been compared with available data from other countries. The calculated absorbed dose rate ranged from 22.33 to 32.66 nGy?h-1 in lo- cation (B) and (E) respectively, which was less than the accepted value.     

Preparation and properties of 117m Sn(IV)-TTHMP in in-vitro and in small animals

In this work,TTHMP was synthesized and labelled with 117m Sn.The preparation conditions,stability and lipophilicity of 117m Sn(IV)-TTHMP were investigated.Biodistribution of the complex in rabbits and mice was studied.It was found that the quantity of TTHMP and pH value of the prepararion solution had vital effects on the labeling yield of 117m Sn(IV)-TTHMP.It was also found that 117m Sn(IV)-TTHMP was hydrophilic and stable at room temperature and 37℃ in open air 117m Sn(IV)-TTHMP showed unexpectedly high bone uptake and bone-to-blood ratio in the animals.This made it potentially useful as an reagent for skeletal scintigraphy and radiotherapy of bone tumors.     

Interaction between uranium and humic acid (Ⅰ): Adsorption behaviors of U(Ⅵ) in soil humic acids

The adsorption behaviors of uranium on three soil humic acids (HAs), which were extracted from soils of different depths at the same site, were investigated under various experimental conditions. The adsorption results showed that U(Ⅵ) in solutions can be adsorbed by the three soil HAs, with the order of FHA (HA from 5 m depth of soil) ＞SHA (HA from the surface) ＞THA (HA from 10 m depth of soil) for adsorption efficiency in each desirable condition, and the adsorption reached equilibrium in about 240 min. Although the maximum adsorption efficiency was adsorption could be described with Langmiur isotherm or Freundlich isotherm equation. The L/S (liquid/solid, mL/g)ratio and pH were important factors influencing the adsorption in our adsorption system besides uranium concentration. The adsorption efficiency decreased with the increase of the L/S ratio and pH at the pH range of 2.0-3.0 for SHA and THA or 2.5 - 6.0 for FHA. However, no significant difference in adsorption of U(Ⅵ) was observed at the experimental temperature. All the results implied that humic substances have different characteristics in samples even collected at the same site.